| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 1 | 用于辐照重化学元素的同位素将核能转化为热的方法以及用于实现该方法的装置（实施例） | CN201510906623.X | 2015-12-09 | CN105513663A | 2016-04-20 | 博格莫洛夫·阿列克西·谢尔盖耶维奇; 贝科夫·安德烈·尤里耶维奇; 莫夏日·维切斯拉夫·米哈伊洛维奇; 奥斯特列措夫·伊戈尔·尼古拉耶维奇 |
| 一种用于辐照重化学元素的同位素将核能转化为热的方法以及一种用于实现该方法的装置涉及重化学元素的核物理化学、核动力工程并更具体地涉及一种用于辐照重化学元素的同位素将核能转化为热的方法和一种通过利用放射性核素并且为此将深度次临界靶暴露于相对论性离子来实现该方法的装置，所述靶包括放射性废料和/或锕系元素和/或乏核燃料。所提出的发明的技术效果是：增加了所产生的热和电力的量以及被处置的放射性废料的量。实现所述方法的装置包括相对论性离子束加速器、用于将束运输并且引入到靶上的单元、补给单元和热变换器单元，所有串联布置。该装置具有在靶段的数目上不同的三个实施例。具有圆锥形或球形形状的单段靶的装置的第一实施例旨在将能量转化为热。除了在相对论性离子束下的能量生产之外，具有圆柱形或圆锥形形状的两段靶的装置的第二实施例使其可能将具有长寿命放射性核素的放射性废料转化成具有短寿命放射性核素的放射性废料。除了第二实施例的优点之外，具有圆柱形或圆锥形形状的三段靶的装置的第三实施例使其可能通过增加靶的第二段中的裂变核素的份额来实现最大动力生产。 | ||||||
| 2 | 微机电系统核电池 | CN201610119087.3 | 2016-03-02 | CN105741900B | 2017-11-03 | 王欣 |
| 本发明公开了一种微机电系统核电池。所述微机电系统核电池包括：基底；悬臂梁结构，所述悬臂梁结构悬空设置，且通过固定端部固定于基底侧壁，所述悬臂梁结构包括放射部分和压电部分，放射部分位于所述悬臂梁结构的自由端部，所述压电部分位于所述悬臂梁结构的固定端部；放射单元，设置在所述基底上的与所述悬臂梁结构的放射部分相对应的位置，用于向所述放射部分发射电子，其中，所述放射部分的宽度大于所述压电部分的宽度。 | ||||||
| 3 | 微机电系统核电池 | CN201610119087.3 | 2016-03-02 | CN105741900A | 2016-07-06 | 王欣 |
| 本发明公开了一种微机电系统核电池。所述微机电系统核电池包括：基底；悬臂梁结构，所述悬臂梁结构悬空设置，且通过固定端部固定于基底侧壁，所述悬臂梁结构包括放射部分和压电部分，放射部分位于所述悬臂梁结构的自由端部，所述压电部分位于所述悬臂梁结构的固定端部；放射单元，设置在所述基底上的与所述悬臂梁结构的放射部分相对应的位置，用于向所述放射部分发射电子，其中，所述放射部分的宽度大于所述压电部分的宽度。 | ||||||
| 4 | 从废乏燃料桶获取的电源 | CN201480013465.9 | 2014-02-27 | CN105009443A | 2015-10-28 | J·T·戴德雷尔 |
| 用于从废乏核燃料桶内产生的衰变热大量提取有用的电功率或机械功率的装置。该功率用于为核燃料桶的主动强制空气热驱散系统提供功率，因此增加该桶的热容量，或者在全厂断电的状况中用于紧急核电厂功率。通过利用存在于废乏核燃料与包围容纳核燃料的桶的部件的环境之间的热梯度来使用热电发电机或其它热机以产生所述功率。 | ||||||
| 5 | 从衰变热产生用于冷却并监视废核燃料池的动力 | CN201280035027.3 | 2012-07-27 | CN103688313A | 2014-03-26 | E·塔特利; J·G·贝勒查克; B·陆; C·A·斯坦斯伯里; C·格勒; M·J·奥斯特罗斯基 |
| 一种在核电站全厂断电情况下用于给废燃料池补水的泵和用于监视废燃料池的传感器持续提供动力的辅助动力源。动力源利用池中废燃料的废热来激活热电模块系统或废热发动机，比如斯特林循环或有机朗肯循环发动机，从而产生用于泵和传感器的动力。辅助动力源还能给冷却系统提供动力以冷却废燃料池。 | ||||||
| 6 | POWER GENERATION FROM DECAY HEAT FOR SPENT NUCLEAR FUEL POOL COLLING AND MONITORING | EP12820360.1 | 2012-07-27 | EP2737493A2 | 2014-06-04 | TATLI, Emre; BELECHAK, Joseph, G.; LU, Baofu; STANSBURY, Cory, A.; GULER, Cenk; OSTROSKY, Michael, Joseph |
| An auxiliary power source for continuously powering pumps for replenishing water in a spent fuel pool and sensors monitoring the pool, in the event of a station blackout at a nuclear plant. The power source uses waste heat from spent fuel within the pool to activate a thermoelectric module system or a waste heat engine, such as a Stirling cycle or organic Rankine cycle engine to generate power for the pump and sensors. The auxiliary power source can also power a cooling system to cool the spent fuel pool. | ||||||
| 7 | 使用済燃料キャスクから得られる電源 | JP2016500446 | 2014-02-27 | JP2016513803A | 2016-05-16 | デデラー、ジェフリー、ティー |
| 使用済原子燃料キャスク内で発生する崩壊熱から有意な量の有用な電力または機械力を取り出すための装置。この電力を利用して、原子燃料キャスク向けの能動的な強制空気除熱システムに給電して当該キャスクの熱容量を高めたり、全交流電源喪失事象時に原子力発電所に非常用電源を提供したりできる。熱電発電装置または他の熱機関が、使用済原子燃料と、当該原子燃料を収容するキャスクの構成機器を取り巻く環境との間の温度勾配を利用して、電力を発生させる。【選択図】図1 | ||||||
| 8 | Power generation by decay heat for cooling and monitoring of spent nuclear fuel pool | JP2014523046 | 2012-07-27 | JP2014525046A | 2014-09-25 | タトゥリ、エムレ; ベレチャク、ジョゼフ、ジー; ル、バオフ; スタンズベリー、コリー、エイ; グラー、センク; オストロスキー、マイケル、ジョゼフ |
| 原子力発電所の全電源喪失時に、使用済燃料プールの水を補給するためのポンプと、プールを監視するセンサとを継続的に給電するための補助電源。 電源はプール内の使用済燃料からの廃熱を利用して、熱電モジュールシステム、あるいはスターリングサイクルまたは有機ランキンサイクルエンジン等の廃熱利用エンジンを作動させ、ポンプとセンサのための発電を行う。 また、補助電源は冷却システムに給電し、使用済燃料プールを冷却することができる。
【選択図】図１ |
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| 9 | A SOURCE OF ELECTRICITY DERIVED FROM A SPENT FUEL CASK | EP14785299 | 2014-02-27 | EP2973985A4 | 2016-11-02 | DEDERER JEFFREY T |
| 10 | A SOURCE OF ELECTRICITY DERIVED FROM A SPENT FUEL CASK | EP14785299.0 | 2014-02-27 | EP2973985A2 | 2016-01-20 | DEDERER, Jeffrey T. |
| Apparatus for extracting useful electric or mechanical power in significant quantities from the decay heat that is produced within spent nuclear fuel casks. The power is used for either powering an active forced air heat removal system for the nuclear casks, thereby increasing the thermal capacity of the casks, or for emergency nuclear plant power in the event of a station blackout. Thermoelectric generators or other heat engines are employed using the thermal gradient that exists between the spent nuclear fuel and the environment surrounding the cask's components housing the nuclear fuel to produce the power. | ||||||
| 11 | POWER GENERATION FROM DECAY HEAT FOR SPENT NUCLEAR FUEL POOL COLLING AND MONITORING | EP12820360 | 2012-07-27 | EP2737493A4 | 2015-04-15 | TATLI EMRE; BELECHAK JOSEPH G; LU BAOFU; STANSBURY CORY A; GULER CENK; OSTROSKY MICHAEL JOSEPH |
| 12 | MICRO-NUCLEAR BATTERY AND ENERGY CONVERSION METHOD THEREOF | US15523352 | 2016-05-23 | US20180118559A1 | 2018-05-03 | Xin Wang |
| The present disclosure discloses a micro-nuclear battery. The micro-nuclear battery comprises a base frame comprising a bottom, a top and a side wall; a cantilever structure having a free end hung in the air and a fixed end fixed to the side wall of the base frame and provided with a piezoelectric component thereon; and a radiation unit comprising an upper radioactive source and a lower radioactive source configured to emit electrons to the free end and respectively arranged at positions in inner surfaces on the top and the bottom of the base frame corresponding to the free end of the cantilever structure, wherein a width of the free end is greater than a width of the fixed end. | ||||||
| 13 | POWER GENERATION FROM DECAY HEAT FOR SPENT NUCLEAR FUEL POOL COOLING AND MONITORING | US13558443 | 2012-07-26 | US20130028365A1 | 2013-01-31 | EMRE TATLI; Joseph G. Belechak; Baofu Lu; Cory A. Stansbury; Cenk Guler; Michael Joseph Ostrosky |
| An auxiliary power source for continuously powering pumps for replenishing water in a spent fuel pool and sensors monitoring the pool, in the event of a station blackout at a nuclear plant. The power source uses waste heat from spent fuel within the pool to activate a thermoelectric module system or a waste heat engine, such as a Stirling cycle or organic Rankine cycle engine to generate power for the pump and sensors. The auxiliary power source can also power a cooling system to cool the spent fuel pool. | ||||||
| 14 | Body heating system | US3737620D | 1969-07-01 | US3737620A | 1973-06-05 | HARVEY D |
| A lightweight, compact, portable, personal body heating system utilizes an inner casing containing a material having a high heat of fusion. A heater is operatively associated with the inner casing for charging the material. A closed recirculating conduit means lies about the inner casing to permit recirculating liquid flow about the casing so that a heat transfer liquid is heated by the heat of fusion of the material. The conduit comprises an inlet tube and an outlet tube permitting passage of the fluid to a body protective device through the outlet tube and recirculation through the inlet tube.
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| 15 | Thermal control and power flattening for radioisotopic thermodynamic power system | US3672443D | 1969-01-28 | US3672443A | 1972-06-27 | BIENERT WALTER B; LEVEDAHL WILLIAM J; STREB ALAN J |
| A thermal control device utilizing the heat pipe principle. Heat receiving and heat rejecting surfaces are spaced from each other along the length of the heat pipe. In a preferred form, a radioisotope fuel capsule is in thermal conducting relationship with the heat receiving surface and a noncondensible gas is mixed with the working fluid of the heat pipe. A noncondensible gas automatically expands as the threshold temperature of the system drops to block off more of the heat rejecting surface. In other alternate preferred embodiments, a nonvaporizable liquid is utilized in lieu of a noncondensible gas to reduce the area of the heat receiving surface as the threshold temperature of the system drops or a second material is mixed with the working fluid which changes to a solid phase to block the flow of the working fluid between the heat rejecting and heat receiving surfaces as the threshold temperature of the system drops.
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| 16 | Radioisotopic power source | US3638023D | 1969-11-07 | US3638023A | 1972-01-25 | COTTAM ALFRED E; CHI JOHN W H; KIM CHANG-KYO; FLAHERTY ROBERT |
| A power source adapted for refueling during operation including a core structure having longitudinal openings for holding radioisotopic fuel elements and longitudinal passageways for passing process fluid flow. Each fuel element opening is sealing separated from the process fluid flow passageways. The process fluid flow passageways are arranged in an even number of annular patterns or passes such that the process fluid inlet and outlet conduits are located at one end of the core. The fuel element openings are accessible at the opposite end of the core to allow fuel replacement without loss of process fluid. A fuel element shipping and transfer cask is adapted to be attached to the heat source opposite the coolant ports for replacing spent fuel elements within the core structure. A passive, self regulating, and recoverable emergency cooling system prevents core melt down on loss of coolant flow.
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| 17 | Hydrospace energy converter | US3543036D | 1967-07-31 | US3543036A | 1970-11-24 | MAJKRZAK CHARLES P |
| 18 | Uncontrolled nuclear decay propulsion and/or power systems | US3447321D | 1965-11-15 | US3447321A | 1969-06-03 | ROMERO JACOB B |
| 19 | Direct cycle radioisotope rocket engine | US50509065 | 1965-10-06 | US3315471A | 1967-04-25 | LEE DAILEY CHARLES; VERDES ESTATES PALOS; FRIEDMAN BURNAM I; MARTINEZ JOHN S; ALLEN EARL W; DONALD JORTNER |
| 20 | Electrostatic propulsion system with a direct nuclear electro generator | US25300663 | 1963-01-21 | US3184915A | 1965-05-25 | LOW JR CHARLES A; MICKELSEN WILLIAM R |
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